Zhi-Gang Mei

Ningbo University — China

Materials Science · Physical Sciences

25h-index2.7kcitations87works2.52yr avg
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Research Topics

Nuclear Materials and Properties(41), Fusion materials and technologies(24), Nuclear reactor physics and engineering(24), High-pressure geophysics and materials(9), Rare-earth and actinide compounds(6)

Publications87 total

Determination of Scale Bar for AGHCF Metallography Data
2025
Response to Wang et al.
Current Biology·2025
Nanotechnology Strategies in Plant Genetic Engineering: Intelligent Delivery and Precision Editing
Plants·2025Open Access
Improved performance of WZO/Cu/WZO transparent conductive films by inserting an ultrathin Cr layer
Ceramics International·2025
Range contraction of the Yangtze finless porpoise inferred from classic Chinese poems
Current Biology·2025· 1 citedOpen Access
Strategies to reduce uric acid through gut microbiota intervention
Frontiers in Microbiology·2025· 3 citedOpen Access
Range contraction of the Yangtze finless porpoise inferred from classic Chinese poems
Current Biology·2025· 4 citedOpen Access
Loss of protistan diversity weakens soil phosphorus availability
Applied Soil Ecology·2025· 7 cited
Engineering efficient carrageenan materials for simultaneously removing herbicide, eight anionic/cationic dyes and metal ion contaminants and adsorption mechanism
International Journal of Biological Macromolecules·2025· 9 citedOpen Access
Intelligent electrochromic photothermal regulation for integrated building energy saving
Energy & Environmental Science·2025· 4 cited
Biosensors for Cardiovascular Health Monitoring
2025
Host genotype‑specific plant microbiome correlates with wheat disease resistance
Biology and Fertility of Soils·2024· 6 cited
Host genotype-specific rhizosphere protists associate soil-borne viral disease resistance in wheat
Plant and Soil·2024· 1 cited
Thermal conductivity of U-Mo alloy fuel
Journal of Nuclear Materials·2024· 2 cited
Range Contraction of Freshwater Megafauna Was Written in Ancient Poems
SSRN Electronic Journal·2024Open Access
Contributions to the mechanistic understanding of the microstructural evolution in irradiated U-Mo dispersion fuel
Journal of Nuclear Materials·2023· 3 citedOpen Access
Fast Reactor Database Utilization for Qualification of Metallic Fuel Forms
2023· 1 citedOpen Access
Computer Vision-aided <i>in situ</i> TEM Studies of Microstructure Evolution under Irradiation
Microscopy and Microanalysis·2023Open Access
Impact of SEM acquisition parameters on the porosity analysis of irradiated U-Mo fuel
Nuclear Materials and Energy·2023· 10 citedOpen Access
Integrated simulation of U-10Mo monolithic fuel swelling behavior
Journal of Nuclear Materials·2023· 7 citedOpen Access
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Frequent Co-authors

Abdellatif M. Yacout(23), Zi‐Kui Liu(14), Shun‐Li Shang(13), Yi Wang(11), Yinbin Miao(9), Kun Mo(7), Linyun Liang(7), Bei Ye(6), G.L. Hofman(5), Yeon Soo Kim(5), Sumit Bhattacharya(5), Lidong Chen(4), Jiong Yang(4), Laura Jamison(4), Long‐Qing Chen(3), Marius Stan(3), Mihai Anitescu(3), Ruqing Xu(3), Jihui Yang(2), Shengqiang Bai(2)